ML19305E337
| ML19305E337 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/26/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19305E338 | List: |
| References | |
| NUDOCS 8004230414 | |
| Download: ML19305E337 (28) | |
Text
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l kN KIG Og#o d
UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION o
g WASHINGTON, D. C. 20555
,/
PHILADELPHIA ELECTRIC CO WANY
_PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT. COMPANY ATLANTIC CITY ELECTRIC C0WANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al., (the licensee) dated January 14, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; l
B.
.The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements t
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
(2) Technical Specifications l
The Technical Specifications contained in Appendices A and i
B, as revised through Amendment No. 65, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
h 8004230
4 3.
This license amendment is effective as of the' date of its issuance.
FOR THE NUCLEAR REGULATORY COPMISSION Mj.yusk Thomas K.'Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 26, 1980 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-44 DOCKE's NO. 50-277 1.
Replace the following paces of the Appendix '"A" Technical Specifications 1
with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert t
35 35 47 47 132 132 i
139 139 165 165 227 227 i
228 228 231 231 232*
232 2.
Add the following new pages:
132a 228*
- Pages 228a and 232 are included due to redistribution of material on the revised pages.
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PBAPS LIMITING' CONDITIONS FOR OPERATION SURVEIIIANCE REOUIREMENTS 3.1 REACTOR PROTECTION SYSTEM 4.' 1 P.2ACER PROTECTION SYSTEM Applicability:
Applicability:
Applies to the instrumenta-Applies to the surveillance tion and associated devices of the instrumentation and which initiate a reactor associated devices which scram.
initiate reactor scram.
Obiective Obiective To assure the operability To specify the type and of the reactor protection frequency of surveillance i
system.
to be applied to the pro-tection instrumentation.
Specification:
Specification:
When there is fuel in the vessel, A. Instrumentation systems the setpoint, minimum number shall be functionally of trip systems, and minimum tested and calibrated number of instrument channels as indicated in Tables that must be operable for 4.1.1 and 4.1.2 each position of the reactor respectively.
mode switch shall be as given in Table 3.1.1. The B. Daily during reactor power designed system response operation, the peak times from the opening heat flux and peaking of the sensor contact up factor shall be checked to and including the and the SCRAM and APRM opening of the trip Rod Block settings given actuator contacts shall by equations in not exceed 100 milli-seconds.
Specification 2.1.A.1 and 2.1.B shall be calculated if the peaking factor exceeds 2.62 for 7x7 fuel, 2.44 for 8x0 fuel, or 2.51 for 8x8R fuel.
i Amendment No.
65 I
PBAPS 3.1 BASES The reactor protection system automatically initiaths a reactor scram to:
1.
Preserve the integrity of the fuel cladding.
2.
Preserve the integrity of the reactor coolant system.
3.
Minimize the energy which must be absorbed following a loss of coolant accident, and present inadvertant criticality.
When there is no fuel in the reactor, the scram serves no function; therefore, the reactor protection system is not required to be operable.
This specification provides the limiting conditions for operation necessary to preserve the ability of the system to perform its intended function even during periods when instrument channels may be out of service because of mainter.ance.
When necessary, one channel may be made inoperable for brief intervals to conduct required functional tests and calibrations.
The reactor protection system is of the dual channel type (Reference subsection 7.2 FSAR).
The system is made up of two independent trip systems, each having two subchannels of tripping devices.
Each subchannel has an input from at least one instrument channel which monitors a critical parameter.
The outputs of the subchannels are combined in a 1 out of 2 logic; i.e. an input signal on either one or both of the subchannels will cause a trip system trip.
The outputs of the trip systems are arranged so that a trip on both systems is required to produce a reactor scram.
This system meets the intent of IEEE - 279 for Nuclear Power Plant Protection Systems.
The system has a reliability greater than that of a 2 out of 3 system and somewhat less than that of a 1 out of 2 system.
With the exception of the Average Power Range Monitor (APRM) channels, the Intermediate Range Monitor (IRM) channels, the Main Steam Isolation valve closure and the Turbine stop valve closure, each subchannel has one instrument channel.
When the minimum condition for operation on the number of operable instrument channels per untripped protection trip system is mat or if it cannot be met and the affected protectims trip system is placed in a tripped cordition, the effectiveness of the protection system is preserved.
l The APRM instrument channels are provided for each protection trip system.
APRM's A and E operate contacts in one subcMnnel and APRM's C and E operate contacts in the other subchannel.
APRM's B, D and F are arranged similarly in Amendment No.
65 -
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PBAPS l
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l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l
t 3 5.F Minimus Low Pressure Coolina 4.5.F Minimus Low Pressure and Diesel Generator Coolium and Diesel Availability Generator Availability
- 1. During any period when one
- 1. When it is determined that one diesel generator is inoper-diesel generator is inoperable a1; able, continued reactor oper-low pressure core cooling and ation is permissible only c on t ain me n t cooling subsystems during the succeeding seven shall be demonstrated to be days unless such diesel gene-operable immediately and daily rator is sooner made operable, thereafter. In addition, the provided that all of the low operabl+ diesel generators pressure core and containment shall be demonstrated to be cooling subsystems and the operable imme diat e ly and daily remaining diesel generators thereafter.
shall be operable.
If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 2. Any combination of inoperable components in the core and containment cooling systems 9
shall not defeat the capabi-lity of the remaining oper-able c omp onent s to fulfill I
the cooling functions.
- 3. When irradiated fuel is in the I
reactor vessel and the reactor is in the Cold Shutdown Condi-tion, both core spray systems, the LPCI and containment cooling subsystems may be inoperable, provided no work is being done which has the potential f or draining the reactor vessel.
4.
During a refueling outage, fuel and LPRM removal and replacement may be 1
perf ormed p rovided at least one of the following conditions below is satisfied.
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klendment No. 65
-132-i
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PBAPS l
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.F.3 (Cont'd) 4.5.F.2 (Cont'd) a.
Both core spray systems and the LPCI system shall be i
operable except that one core spray system or the LPCI system may be in-operable f or a period of thirty days, et
- b. The reactor vessel head is removed, the cavity is l
flooded, the spent fuel pool gates are removed, and the water level is maintained at least 21 feet over the t op of irradiated fuel assemblies seated in the spent f uel storage p ool racks and no work is being p erf orr,e d which has the potencial f or draining the repator vessel.
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65
-132a-l l
PBAPS 3 5.E, BASES (Cont 'd. )
Nith one ADS valve known to be incapable of automatic operation, four valves remain operable to perf orm th.eir ADS function.
However, since the ECCS Loss-of-Coolant Accident analysis for small line breaks assumed that all five ADS valves were op e ra ble,
reactor operation with one ADS valve. inoperable is only allowed to continue f or seven (7) days provided that the HPCI system is demonstrated to be operable and that the actuation logic f or tae (remaining) f ou r ADS valves is demons t rated to be operable.
The ADS test circuit permits continued surveillance on the operable I
relief valves t o a s s u r e.t h a t they will be available if required.
F.
Minimum Low Pressure Cooling and Diesel Generator Availability The pu rp os e of Specification F is to assure that adequate core cooling capability is available at all times.
It is during refueling outages that major maintenance is perf ormed and during such time that all low pressure core cooling systems may be out of service.
This specification p rovides that should this occur.
no work will be perf ormed on the p rimary system which could lead to draining the vessel.
This work would include work on certain control rod drive comp onent s and recirculation system.
Additionally, the specification provides minimum core flooding requirements during refueling op e ra t i ons.
Specification 3 9 must als o be consulted t o de termine other requirements for the diesel generators.
G.
Maintenance of Filled Discharge Pipe if the discharge piping of the core spray, LPCI subsystem, HPCI, and RCIC are not filled, a water hamme r can develop in this piping when the pump and/or pumps are started.
If a water hammer were to occur at the time at which the system were required, the system would s till perf orm its design function.
However, to minimize damage to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system is in an operable condition.
-139-klendment No. 65
i PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 37 C ONT AI NM ENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Applicability:
' Applicability:
Applies to the operating Applies to the p rimary and status of the p rimary and secondary containment secondary containment integrity.
systems.
Objective:
Objective:
To assure the integrity of To verify the integrity of the primary and secondary the primary and secondary containment system.
containment.
Specification:
Specification:
A.
- 1. The suppression chamber water level and temperature
- 1. Whenever the. nuclear shall be checked once per system is pressurizad day.
above atmospheric p ressure or work is being done 2.
a.
Whenever there is in-which has the potential dication of relief valve i
to drain the vessel, operation (e xcep t when the pressure suppression the reactor is being p ool water volume shutdown and torus and temperature shall be cooling is being es-maintained within the tab 11shed) or testing following limits except which adds heat to the as specified by suppression p ool, the 3.7.A.2, or when inopera-pool temperature shall bility of the core spray be continually monitored systems, the LPCI and and also observed and containment cooling sub-logged eve ry 5 minutes systems is permissible until the heat addition as provided f or in is terminated.
3.5.F.3 and 3.5.F.4.b.
a.
Minimum water volume-
- 3. Whenever there is indication 122.900 ft 3 of relief valve operation with the temperature of the b.
Maximum water volume-suppression pool reaching 160'F; 127,300 ft 3 or more and the p rima ry coolant' system pressure greater than 200 psig, an external visual examination of the suppression chamber shall be conducted before res umin g p owe r operation; i
4.
A visual inspection of the sup-p re s s i on chamber interior, in-ciuding water line regions shal.
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be made at each major refueling l
Amendment No.
65
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.10. A. S.b (Cont'd) 4.10.A directional control valves for remaining control rods shall be disarmed electrically and sufficient margin to i
criticality shall be demonstrated.
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- c. If maintenance is to be i
performed on two control rod l
drives, they unast be separated l
by more than two control cella j
in any direction.
- d. An appropriate number of SRM's are available as defined in i
specification 3.10.B.
- 6. Any number of control rods may be withdrawn or removed from the reactor core provided the following conditions are satisfied:
- a. The reactor mode switch is locked in the " refuel" position.
The ref mling interlock which prevents more than one control rod from being withdrawn may be bypassed on a withdrawn control rod after the fuel assemblies in the cell containing (controlled by) that control rod have been removed from the reactor core.
All other refueling interlocks shall be operable.
3.
Core Monitoring B.
Core Monitoring 1.
Except as specified in 3.10.B.2, 1.
Prior to making any alterations 3.10.B.3, 3.10 B.4 and 3.10.B.5, to the core, the SRM's shall be during core alterations two SRM's functionally tested and checked shall be operable, one in the for neutron response. Thereafter, core quadrant where fuel or while required to be operable, controls rods are being moved and the SRM's will be checked daily one in the adjacent quadrant.
for response.
For an SRM to be considered operable, the following conditions shall be satisfied:
Amendment No.
65 i
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i PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.10.B (Cont'd) 4.10.B (Cont'd) l Prior to unloading or i
- a. The SRM shall be inserted to 2..
reloading of fuel as provided the normal operating level.
(Use of special movable, for in sections 3.10.B.2 6 dunking type detectors during 3.10.B.3, the SRM's l
fuel loading and major core shall be functionally tested.
alterations in place of normal Prior to unloading of fuel, detectors is permissible the SRM's should also be as long as the detector checked for neutron response.
is connected to the normal SRM circuit.)
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- b. The SRM shall have a minimum of 3 cps with all rods fully inserted in the core.
2.
Prior to unloading of fuel, the SRM's shall be proven operable as i
stated above; however, during unloading of fuel, the SRM count rate may drop below 3 cps, provided all control rods are full inserted and rendered
)
electrically inoperable with the exception of the following provision.
Individual control j
rods outside the periphery of the then existing fuel matrix may be electrically armed and moved after all fuel in the cell containing that control rod have been removed from the reactor Core.
3.
Prior to reloading of fuel, two, three, or four fuel assemblies may be returned to their previous core positions adjacent to each of the 4 SRM's to obtain the required 3 cps.
Until these assemblies are loaded, the SRM 3 cps count rate is not required.
- 4. The SRM 3 cps count rate is not required with all fuel removed from the core.
- 5. During the unloading and reloading of fuel, intermediate arrays of fuel shall always contain at least one SRM.
Amendment No. 65
-228-i l
P8APS C.
Spent Fuel Pool Water Level C.
Spent Fuel Pool Water Level Whenever irradiated fuel is stored Whenever irradiated fuel is stored in the spent fuel pool, the pool in the spent fuel pool, the water l
water level shall be maintained at level shall be recorded daily, l
or above 8 1/28 above the top of the fuel.
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D.
Heavy Loads Over Spent Fuel Loads in excess of 1000 lbs (excluding the rigging and transport vehicle) shall be prohibited from travel over fuel assemblies in the spent fuel storage pool.
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65
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PBAPS 3.10 BASES (Cont' d) j The requirements for SRM Operability dua.ing these core alterations j
essure sufficient core monitoring, i
i B.
Core Monitoring l
The SRM's are provided to monitor the core during periods of station chutdown and to guide the operator during refueling operations and 4
station startup.
Requiring two operable SRM's in or adjacent to any I
core quadrant where fuel or control rods are being moved assures cdequate monitoring of that quadrant during such alterations.
The requirement of 3 counts per second provides assurance that neutron flux is being monitored and insures that startup is conducted only if the source range flux level is above the minimum assumed in the control rod drop accident.
During unloading of fuel, it is permissible to allow the SRM count rate to decrease below 3 cps.
Since all fuel moves during core unloading will reduce reactivity, the lower number of counts will not present a hazard.
Requiring the SRM's to be functionally tested prior to fuel removal assures that the SRM's will be operable at the start of fuel removal.
The daily response check of the SRM's ensures their continued operability until the count rate deminishes due to fuel removal.
Control rods in cells from which all fuel has been removed and which are outside the periphery of the then existing fuel matrix may be armed electrically and moved for maintenance purposes during fuel removal, provided all rods that control fuel are fully inserted and electrically disarmed.
During core loading, the loading of adjacent assemblies around the four SRM's before attaining the 3 cps is permissible because these essemblies were in a subcritical configuration when they were removed and therefore will remain subcritical when the same assemblies are placed back into their previous positions.
Since specification 3.10.A.2 requires that all control rods be fully inserted prior to loading fuel, inadvertent critical whenity is precluded during core loading.
C.
Spent Puel Pool Water Level To assure that there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established.
The minimum water level of 8 1/2' above the top of the fuel is established because it provides adequate shielding and is well above the level to assure adequate cooling.
/Wendment No. 65
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PBAPS i
i 4.10 BASES A.
Refueling Interlocks Complete functional testing of all refueling interlocks before any refueling outage will provide positive indication that the interlocks operate in the sittu tions for which they were designed.
By loading each hoist with a weight equal to the fuel assembly, positioning the i
refueling platform and withdrawing control rods, the interlocks can be l
subjected to valid operational tests.
Where redundancy is provided in the logic circuitry, tests can be performed to assure that each redundant logic element can independently perform its functions.
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B.
Core Monitoring Requiring the SRM's to be functionally tested prior to any core i
alteration assures that the SRM's will be operable at the start of that alteration.
The daily response check of the SRM's ensures their l
continued operability.
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64 l
- 232 -
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UNITED STATES 8"
NUCLEAR REGU'LATORY COMMISSION n
- c WASHINGTON. D. C. 20555
(
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PHILADELPHIA ELECTRIC COWANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT C0W ANY ATLANTIC CITY ELECTRIC COW ANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al., (the licensee) dated January 14, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No. OPR-56 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
mvv.ioou
3.
This license amendment is effective as of the date of its issuance.
i FOR THE NUCLEAR REGULATORY COPMISSION Thomas $.Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications l
Date of Issuance: March 26, 1980 i
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N ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO.50-27d 1.
Replace the following pages of the Appendix "A" Technical Specifications with i
the enclosed pages. The revised pages are identified by amendment number and e
contain vertical lines indicating the area of change.
Remove Insert 35 35 47 47 132 132 139 139 165 165 227 227 228 228 231 231 232*
232 2.
Add the following new pages:
132a 228a*
- Pages 228a and 232 are included due to redi;+Mbution of material on the revised pages.
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PBAPS i
LIMITING CONDITIONS FOR OPERATION SURVEIILANCE REQUIREMENTS
[
t 3.1 REAC'IOR PROTECTION SYSTEM 4.1 REAC'1VR PROTECTION SYSTEM Applicability:
Applicability:
i Applies to the instrumenta-Applies to the surveillance tion and associated devices of the instrumentation and which initiate a reactor associated devices which initiate reactor scram.
Obiective Obiective To assure the operability To specify the type and i
of the reactor protection frequency of surveillance system.
to be applied to the pro-l tection instrumentation.
Specification:
Specification:
(
When there is fuel in the vessel, A.
Instrumentation systems l
the setpoint, minimum number shall be functionally of trip systems, and minimum tested and calibrated l
number of instrument channels as indicated in Tables i
that must be operable for 4.1.1 and 4.1.2 i
each position of the reactor respectively.
mode switch shall be as given in Table 3.1.1. The B. Daily during reactor power designed system response operation, the maximum frac-
' times from the opening tion of limiting density of the sensor contact up factor shall be checked to and including the and the SCRAM and APRM i
opening of the trip Rod Block settings given actuator contacts shall by equations in not exceed 100 milli-seconds.
Specification 2.1.A.1 and 2.1.B shall be calculated if the maximum fraction of limiting power density exceeds the fraction of rated power.
Amendment No. 64 l
I PBAPS 3.1' BASES The reactor protection system automatically initiates a reactor i
scram to:
1.
Preserve the integrity of the duel cladding.
2.
Preserve the integrity of the reactor coolant syttom.
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3.
Minimize the energy which must be absorbed following a loss of coolant accident, and present inadvertant criticality.
When there is no fuel in the reactor, the scram serves no function; therefore, the reactor protection system is not required to be operable.
This specification provides the limiting conditions for operation necessary to preserve the ability of the system to perform its intended function even during periods when instrument channels may be out of service because of maintenance.
When necessary, one channel may be made inoperable for brief intervals to conduct required functional tests and calibrations.
The reactor protection system is of the dual channel type (Reference subsection 7.2 FSAR).
The system is made up of two independent trip systems, each having two subchannels of tripping j
devices.
Each subchannel has an input from at least one instrument channel which monitors a critical parameter.
The outputs of the subchannels are combined in a 1 out of 2 logic-i.e. an input signal on either one or both of the subchannels will cause a trip system trip.
The outputs of the trip systems are l
arranged so that a trip on both systems is required to produce a reactor scram.
This system mects the intent of IEEE - 279 for Nuclear Power Plant Protection Systems.
The system has a reliability greater than that of a 2 out of 3 system and somewhat less than that of a 1 out of 2 system.
1 With the exception of the Average Power Range Monitor (APRM) channels, the Intermediate Range Monitor (IRM) channels, the Main i
steam Isolation valve closure and the Turbine stop valve closure, each subchannel has one instrument channel.
When the minimum condition for operation on the number of operable instrument channels per untripped protection trip system is met or if it cannot be met and the affected protection trip system is placed in a tripped condition, the effectiveness of the protection system is preserved.
The APRM instrument channels are provided for each protection trip system.
APRM's A and E operate contacts in one subchannel and APRM's C and E operate contacts in the other subchannel.
APRM's B, D and F are arranged similarly in Amendment No. 64
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.F Minimus Low Pressure Cooling 4.5.F Minimum Low Pressure and Diesel Generator Coolina and Diesel Availability Generator Availability
- 1. During any period when one
- 1. When it is determined that one diesel generator is inoper-diesel generator is inoperable.a1 able, continued reactor oper-low pressure core cooling and ation is permissible only containment cooling subsystems during the succeeding seven shall be demonstrated to be days unless such diesel gene-operable immediately and daily rator is sooner made operable, thereafter. In addition, the provided that all of the low operable diesel generators pressure core and containment shall be demonstrated to be cooling subsystems and the operable immediately and daily remaining diesel generators thereafter.
shall be operable.
If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor l
shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 2. Any combination of inoperable c omp onent s in the core and containment cooling systems shall not defeat the capabi-lity of the remaining oper-able components to fulfill the cooling functions.
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- 3. When irradiated fuel is in the reactor vessel and the reactor is in the Cold Shutdown Condi-l tion, both core spray systems, the LPCI and containment cooling subsystems may be inoperable, provided no work is being done which has the potential f or draining the reactor vessel.
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- 4. During a refueling outage, fuel and LPRM removal and replacement may be perf ormed provided at least one of the following conditions below is satisfied:
Amendment No.
64
-132-
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.F.3 (Cont'd) 4 5.F.2 (Cont'd) a.
Both core spray systems and the LPCI system shall be operable except that one core spray system or the LPCI system may be in-operable for a period of thirty days, or
- b. The reactor vessel head is removed, the cavity is flooded, the spent f uel pool gates are removed, and the water level is maintained at least 21 feet over the top of irradiated fuel assemblies sestaJ in the spent fuel storage p ool racks and no work is being perf ormed which has the l
potential f or draining the reactor vessel.
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l Amendment No. 64
-132a-i
PBAPS 3.5.E BASES (Cont'd.)
Vith one ADS valve known to be incapable of automatic operation, four valves remain operable to perf orm their ADS function.
However, since the ECCS Loss-of-Coolant Accident analysis for small line breaks assumed that all five ADS valves were operable, reactor operation with one ADS. valve Inoperable is only allowed to continue for seven (7) days provided that the HPCI system is demonstrated t o be operable and that the actuation logic f or the (remaining) f our ADS valve s is demons t rated t o be operable.
The ADS test circuit permits continued surveillance on the operable relief valves to assure that they will be available if required.
F.
Minimum Low Pressure Cooling and Diesel Generator Availability The purp os e of Specification F is to assure that adequate core cooling capability is available at all times.
It is du rin g refueling outages that major maintenance is perf ormed and during such time that all low pressure core cooling s y s t e ms may be out of service.
This specification p rovides that should this occur, no work will be perf ormed on the p rima ry system which could lead t o draining the vessel.
This work would include work on certain control rod drive c omp onent s and recirculation system.
Additionally, the specification provides minimum core flooding requirements during refueling operations.
Specification 3.9 must als o be consulted t o de te rmine other requirements for the diesel generators.
G.
Maintenance of Filled Discharge Pipe If the discharge p ip in g of the core spray, LPCI subsystem, HPCI, and RCIC are not filled, a water hamme r can de ve lop in this 4
piping when the pump and/or pumps are started.
If a water hammer were t o occu r at the time at which the system were required, the system would s till perf orm its design function.
However, to minimize damage to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system is in an operable condition.
Amendment No. 64
-139-l l
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 37 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Applicability:
. Applicability:
Applies to the operating Applies to the p rimary and status of the p rimary and secondary containment secondary containment integrity.
systems.
l Objective:
Obiectiver i
To assure the integrity of To verify the integrity of the primary and secondary the primary rad secondary containment system.
contsinnent.
Specification:
Specificacion:
- 1. The suppression chambar water level and temperature
- 1. Whenever the nuclear shall be checked once per system is pressurized day.
above atmospheric p ressure or work is being done 2.
a.
Whenever there is in-which has the potential dication of relief valve to drain the vessel, operation (e xc ep t when the pressure suppression the reactor is being p ool water volume shutdown and torus and temperature shall be cooling is being es-maintained within the tablished) or testing following limits except which adds heat to the as specified by suppression p ool, the 3.7.A.2, or when inopera-pool temperature shall bility of the core spray be continually monitored i
systems, the LPCI and and also observed and containment cooling sub-logged every 5 minutes systems is permissible until the heat addition j
as provided f or in is terminated.
3.5.F.3 and 3.5.F.4.b.
I a.
Minimum water volume-
- 3. Whenever there is indication 122,900 ft 3 of relief valve operation with the temperature of the b.
Maximum water volume-suppression p ool reaching 160'FI 127,300 ft 3 or more and the p rima ry coolant system pressure greater than 200 psig, an external visual examination of the suppression l
chamber shall be conducted before resuming p owe r operation l
- 4. A visual inspection of the sup-pression chamber interior, in-cluding water line regions shal l
be made at each major refueling outage.
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PBAPS o
I LIMITING CONDITIONS FOR OPE'.TICN SURVEILLANCE REQUIREME!CS 3.10. A. S.b (Cont'd) 4.10.A directional control valves for remaining control rods shall be disarmed electrically and l
sufficient margin to i
criticality shall be demonstrated.
- c. If maintenance is to be performed on two control rod drives, they must be separated by more than two control cells in any direction.
- d. An appropriate number of SRM's are available as defined in specification 3.10.B.
j
- 6. Any number of control rods may be withdrawn or removed from the reactor core provided the following conditions are satisfied:
- a. The reactor mode switch is locked 1.; the " refuel" position.
The refueling interlock which prevents more than one control rod from being withdrawn may be bypassed on a withdrawn control rod after the fuel assemblies in the cell containing (controlled by) that control rod have been removed from the reactor core.
All other refueling interlocks shall be operable.
3.
Core Monitoring B.
Core Monitoring 1.
Except as specified in 3.10.B.2, 1.
Prior to making any alterations 3.10.B. 3. 3.10.B.4 and 3.10.B.5, to the core, the SRM's shall be during core alterations two SRM's functionally tested and checked shall be operable, one in the for neutron response. Thereafter, core quadrant where fuel or while required to be operable, controls rods are being moved and the SRM's will be checked daily one in the adjacent quadrant.
for response.
For an SRM to be considered operable, the following conditions shall be satisfied:
Amendment No.
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.10.B (Cont'd) 4.10.B (Cont'd)
- a. The SRM shall be inserted to 2;
Prior to unloading or the normal operating level.
reloading of fuel as provided (Use of special movable, for in sections 3.10.B.2 6 dunking type detectors during 3.10.B.3, the SRM's fuel loading and major core shall be functionally tested.
alterations in place of normal Prior to unloading of fuel, detectors is permissible the SRM's should also be as long as the detector checked for neutron response.
is connected to the i
normal SRM circuit.)
- b. The SRM shall have a minimum of 3 cps with all rods fully inserted in the core.
- 2. Prior to unloading of fuel, the i
SRM's shall be proven operable as stated above; however, during i
unloading of fuel, the SRM count rate may drop below 3 eps, provided all control rods are full inserted and rendered electrically inoperable with the exception of the following provision.
Individual control rods outside the periphery of the i
then existing fuel matrix may be electrically armed and moved after all fuel in the cell containing that control rod have been removed from the reactor Core.
l 3.
Prior to reloading of fuel, two, three, or four fuel assemblies may be returned to their previous core positions adjacent to each of the 4 SRM's to obtain the required 3 cps.
Until these i
aseemblies are loaded, the SRM 3 cps count rate is not required.
4.
The SRM 3 cps count rate is not required with all fuel removed from the core.
- 5. During the unloading and reloading of fuel, intennediate arrays of fuel shall always contain at least one SRM.
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L PBAPS C.
Spent Fuel Pool Water Level C.
Spent Fuel Pool Water Level i
whenever irradiated fuel is stored whenever irradiated fuel is stored in the spent fuel pool, the pool in the spent fuel pool, the water water level shall be maintained at level shall be recorded daily, i
or above 8 1/2' above the top of the fuel.
D.
Heavy Loads Over Spent Fuel l
Loads in excess of 1000 lbe (excluding i
the rigging and transport vehicle) shall be prohibited from travel over fuel assemblies in the spent fuel storage pool.
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Amendment No. 64
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PBAPS i
3.10 BASES (Cont' d) l The requirements for SRM Operability during ' hese core alterations f
t assure sufficient core monitoring.
B.
Core Monitorinq l
1 The SRM's are provided to monitor the core during periods of station chutdown and to guide the operator during refueling operations and station startup.
Requiring two operable SRM's in or adjacent to any core quadrant where fuel or control rods are being moved assures cdequate monitoring of that quadrant during such alterations.
The i
requirement of 3 counts per second provides assurance that neutron flux is being monitored and insures that startup is conducted only if i
the source range flux level is above the minimum assumed in the control rod drop accident.
During unloading of fuel, it is permissible to allow the SRM count rate to decrease below 3 eps.
Since all fuel moves during core I
unlogding will reduce reactivity, the lower number of counts will not present a hazard.
Requiring the SRM's to be functionally tested prior to fuel removal assures that the SRM's will be operable at the start of fuel removal.
The daily response check of the SRM's ensures their continued operability until the count rate deminishes due to fuel l
removal.
Control rods in cells from which all fuel has been removed l
and which are outside the periphery of the then existing fuel matrix may be armed electrically and moved for maintenance purposes during fuel removal, provided all rods that control fuel are fully inserted and electrically disarmed.
During core loading, the loading of adjacent assemblies around the four SRM's before attaining the 3 cps is permissible because these assemblies were in a subcritical configuration when they were removed and therefore will remain subcritical when the same assemblies are placed back into their previous positions.
Since specification 3.10. A.2 requires that all control rods be fully inserted prior to loading fuel, inadvertent critical whenity is precluded during core loading.
C.
Spent Fuel Pool Water Level To assure that there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established.
The minimum water level of 8 1/2' above the top of the fuel is established because it provides adequate shielding and is well above the level to assure adequate cooling.
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l PBAPS 4.10 BASES i
A.
Refueling Interlocks I
complete functional testing of all refueling interlocks before any j
refueling outage will provide positive indication that the interlocks operate in the situations for which they were designed.
By loading i
each hoist with a weight equal to the fuel assembly, positioning the refueling platform and withdrawing control rods, tne interlocks can be subjected to valid operational tests.
Where redundancy is provided in the logic circuitry, tests can be performed to assure that each redundant logic element can independently perform its functions.
B.
Core Monitoring Requiring the SRM's to be functionally tested prior to any core alteration assures that the SRM's will be operable at the start of that alteration.
The daily response check of the SRM's ensures their i
continued operability.
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l Amendment No.
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